ML18024B113
| ML18024B113 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/12/1979 |
| From: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML18024B114 | List: |
| References | |
| NUDOCS 7911270077 | |
| Download: ML18024B113 (4) | |
See also: IR 05000259/1979028
Text
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In Reply Refer To:
RII:DSP
50-259/79-28
.50-260/79-28
50-296/79-28
UNITEDSTATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100
ATLANTA,GEORGIA 30303
OCT 1 g gyp
Valley Authority
Attn:
H. G. Parris
Manager of Power
500A Chestnut Street
Tower II
Chattanooga,
TN
37401
Gentlemen:
Concerning our letter of October 9,
1979 which enclosed
NRC Region II
inspection report nos.
50-259/79-28,
50-260/79-28
and 50-296/79-28.
Please substitute
the enclosed inspection report page
3 for the one
which was included in the report sent to you.
Paragraph
8 of this
report was inadvertently omitted.
Sincerely,
E.c.
R.
C.
ewis, Acting Chief
Reactor Operations
and
Nuclear
Support Branch
cc:
H. L. Abercrombie
Plant Superintendent
Post Office Box 2000
Decatur,
35602
D. E. McCloud
Project Engineer
400 Chestnut Street
Tower II
Chattanooga,
37401
l ~
J. F.
Cox
400 Commerce Street
W10C131 C-K
Knoxville, Tennessee
37902
E.
G. Beasley
Valley Authority
309 Grant's Building
Knoxville, Tennessee
37902
0
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OCl l g pe
During this period of thee reactor'ressure
was controlled by the main
steam safety/refief valves,
and vessel, level by the High Pressuxe
Coolant
Infection and Reactor
Core Isolation Cooling
(RCXC) systems.
During a visual'inspection
by the licensee'f
the
RCXC turbine, water was
observed issuing from the turbine shaft steam seals
and the governor valve
leakoff line.
The turbine was secured
and the problem investigated.
It
was determined that water had backed
up from the barometric
condenser into
the steam seal
and valve leakoff lines and had entered
the RCIC oil system.
The water back up was caused
by a problem with the barometric'condensex
condensate
pump ~hose breaker
was found in the tripped position.
In
addition,
a stop check valve (71-32) on, the discharge of the barometric
condenser
vacuum pump had failed to open, preventing the pump from drawing
a vacuum on the condenser.
The oil system was drained
and refilled and the RCIC system tested satis-
factorily with no recurrence
of the problems.
The licensee is still
investigating the cause of the condensate
pump breaker trip.
Opexating
personnel
are being cautioned to test stop check valves which have been
manually shut and then opened to insure they are not stuck on their shut
seat.
The inapectoz witnessed
the startup of the Unit 3 reactor
on September
17,
1979.
This included approach
to criticality, criticality, and power
increase
to the heating range.
The inspector did not identify any safety
concerns of the startup.
No items of noncompliance
or deviations were identified.
Licensee
Event
Re orts
On July 31;
1979,
a failed Unit
1 smoke detector
(XS-39-106PC)
was
discovered
by licensee personnel.
It was replaced
and tested satisfactorily.
Technical Specification (TS) 3.11.C.1 states
that all smoke detectors
must
be operational except that one may be inoperable for,no greater
than 30
days.
T. S. 6.7.b.(2) requires that operation in a degraded
mode be the
.
subject,of
a thirty-day written report from the licensee to the NRC.
No
thirty-day report was submitted by the licensee
and this act was questioned
by the inspector,'he
licensee
contended
that one smoke detector which
was failed for no greater
than 30 days did not violate the operability
criteria of T. S. 3.11.C.1 stated
above.
Unresolved Item:
This matter of failure to submit
a thixty-day written
report concerning
an inoperable
smoke detector is considered
an unxesolved
i'tern pending followup, by the inspector, of the xepoxtability requirements
of this item,